Apparatus for removing thermal sleeve from cold leg of reactor coolant system
원문보기
IPC분류정보
국가/구분
United States(US) Patent
등록
국제특허분류(IPC7판)
G21C-015/00
G21C-019/00
출원번호
US-0760060
(2010-04-14)
등록번호
US-8243870
(2012-08-14)
우선권정보
KR-10-2009-0123774 (2009-12-14)
발명자
/ 주소
Baek, Won Jong
Jang, Sung Ho
Lee, Bum Suk
Song, Ki Tae
출원인 / 주소
KPS Co., Ltd.
대리인 / 주소
Lucas & Mercanti, LLP
인용정보
피인용 횟수 :
0인용 특허 :
14
초록▼
Disclosed is an apparatus for removing a thermal sleeve from a cold leg of a reactor coolant system, which removes an unintentionally separated thermal sleeve without pipe cutting, preventing invasion of impurities into pipes and achieving reliable pipe re-welding. The apparatus includes a sleeve re
Disclosed is an apparatus for removing a thermal sleeve from a cold leg of a reactor coolant system, which removes an unintentionally separated thermal sleeve without pipe cutting, preventing invasion of impurities into pipes and achieving reliable pipe re-welding. The apparatus includes a sleeve removal tool including a corn head formed at a shaft, a pressure plate below the corn head to maximize hydraulic pressure inside a safety injection pipe, a spring connected to the pressure plate to keep the pressure plate unfolded, and a guide wheel to guide the sleeve removal tool into the safety injection pipe, a horizontal movement carrier including bodies connected to each other by a link, a seating rod for seating of the sleeve removal tool, and moving wheels for movement of the horizontal movement carrier, and a vertical movement carrier including first and second anti-separation bars to prevent separation of the horizontal movement carrier.
대표청구항▼
1. An apparatus for removing a thermal sleeve from a cold leg of a reactor coolant system, the thermal sleeve being installed to minimize the effect of thermal shock at a junction between a coolant pipe of a reactor and a safety injection pipe connected to a midway position of the coolant pipe, the
1. An apparatus for removing a thermal sleeve from a cold leg of a reactor coolant system, the thermal sleeve being installed to minimize the effect of thermal shock at a junction between a coolant pipe of a reactor and a safety injection pipe connected to a midway position of the coolant pipe, the apparatus comprising: a sleeve removal tool including a corn head formed at a front end of a shaft having a predetermined length, a pressure plate provided below the corn head to maximize the effect of hydraulic pressure inside the safety injection pipe, the pressure plate being divided into a plurality of sections so as to be folded or unfolded, a spring connected to an upper surface of the pressure plate to keep the pressure plate in an unfolded state, and a guide wheel provided at a midway position of the shaft to guide the sleeve removal tool into the safety injection pipe:a horizontal movement carrier including a plurality of bodies connected to each other by use of a link, a seating rod into which the sleeve removal tool is seated and coupled, and moving wheels installed to the respective bodies so as to allow the horizontal movement carrier to horizontally slide and move along the coolant pipe; anda vertical movement carrier including first and second anti-separation bars provided respectively at front and rear ends thereof to prevent the horizontal movement carrier from being separated from the vertical movement carrier during upward or downward movement thereof inside the reactor, the second anti-separation bar located at the front end of the vertical movement carrier being pivotally rotatable about a hinge. 2. The apparatus according to claim 1, further comprising an extension pipe connected to the safety injection pipe for connection of wire ropes required for remote movement of the sleeve removal tool and the horizontal movement carrier, wherein the extension pipe has a bent lower end portion obliquely extending toward the coolant pipe by a predetermined guidance angle, andwherein a flange cover is provided at a coupling region of the extension pipe and the safety injection pipe to prevent fluid leakage under the effect of the hydraulic pressure inside the safety injection pipe. 3. The apparatus according to claim 1, wherein a slider ring is movably installed to the shaft of the sleeve removal tool, and a tension release link is provided to connect the pressure plate and the slider ring to each other. 4. The apparatus according to claim 1, wherein an introduction eyebolt for connection of an introduction wire rope is installed at the front end of the shaft of the sleeve removal tool, and a pulling eyebolt for connection of a pulling wire rope is installed at a rear end of the shaft. 5. The apparatus according to claim 4, wherein the slider ring has a wire connection loop for connection of a wire rope required to forcibly release a tensile force applied to the pressure plate. 6. The apparatus according to claim 3, wherein an introduction eyebolt for connection of an introduction wire rope is installed at the front end of the shaft of the sleeve removal tool, and a pulling eyebolt for connection of a pulling wire rope is installed at a rear end of the shaft. 7. The apparatus according to claim 6, wherein the slider ring has a wire connection loop for connection of a wire rope required to forcibly release a tensile force applied to the pressure plate. 8. The apparatus according to claim 1, wherein the bodies of the horizontal movement carrier respectively have cutout edges facing each other. 9. The apparatus according to claim 1, wherein the horizontal movement carrier has a wire connection loop for connection of the introduction and pulling wire ropes, and the wire connection loop is formed at the same position as the seating rod. 10. The apparatus according to claim 8, wherein the horizontal movement carrier has a wire connection loop for connection of the introduction and pulling wire ropes, and the wire connection loop is formed at the same position as the seating rod.
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이 특허에 인용된 특허 (14)
Grant C. Jensen, Apparatus and methods for replacing a core spray T-box/thermal sleeve in a nuclear reactor.
Latreille,Pascal; Channussot,Jean Michel, Procedure and means for replacing and procedure for repairing a section of a pipe in the primary circuit of a nuclear reactor.
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